ML20041D869

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Pump & Valve Inservice Testing Program
ML20041D869
Person / Time
Site: Sequoyah  
Issue date: 02/03/1982
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20041D865 List:
References
PROC-820203, NUDOCS 8203090382
Download: ML20041D869 (85)
v • d • e


Text

{{#Wiki_filter:... =_.... _... - =_m l 1 di l ~ tl 1-T el'l 2 1 l r 4, 41 f 4' SEQUOYAH NUCLEAR PLANT j i ! UNITS 1 AND 2 e i PUNP AND VALVE { i INSERVICE TESTING PROGRAM i i I l Submitted: 2/3/82 't Date l 2 1 J s ? + i i 4 3. E 1 i 4 ' s k l t -g r i. i-f 8203090382 820303 t PDR ADOCK 05000327 1 p PDR

'i TABLE OF CONTENTS Section Title Page li bj

1.0 INTRODUCTION

1 2.0 PUMP INSERVICE TESTING PR0 CRAM............................. 1 2.1 PUMP TESTING FREQUENCY..................................... 1 3.0 VALVE INSERVICE TESTING PR0 GRAM............................ 2 3.1 CATECORY A VALVES.......................................... 2 l ~ 3.2 THERMAL RELIEF VALVES...................................... 2 3.3 THERMAL RELIEF CHECK VALVES................................ -3 3.4 CORRECTIVE ACTI0N.......................................... 3 3.5 SYSTEMS OUT OF SERVICE..................................... 3 3.6 EMERGENCY DIESEL SYSTEMS................................... 3 7 1p-p 3.7 FAIL-SAFE ACTUATORS........................................ 4 o p 3.8 VALVE TIMING AND REMOTE INDICATION......................... 4 0 b 3.9 PASSIVE VALVE.............................................. 4 o 1 3 3.10 COLD SHUTDOWN TESTING...................................... 4 APPENDIX A................................................. A-1 APPENDIX B................................................. B-1 a APPENDIX C................................................. C-1

i APPENDIX D.................................................

D-1 1 '~ -y ~

. i. i 4 APPENDIX A i SEQUOYAH PUMP INSERVICE TESTING PROGRAM i Summarv of Information Provided I The pump test table (Table A) provides the following information on testing requirements: I 1. System l 2. Drawing on which the pump is depicted 3. Speed l 4. Inlet Pressure 5. Differential Pressure 4 4-i 6. Flow Rate j 7. Vibration Amplitude 8. Observation of Lube Oil Level / Pressure i 9. Bearing Temperature o b-i A-1

.t p. ) ' s I Y i "i ! i - NOTES I t 1. Synchronous or induction motor driven pumps do not require speed check per IWP-4400. 2. Flow rate is not required since this pump is tested in a fixed resistance j pathway. Relief is requested from the 1977 Edition through Summer 1978 Addenda for Unit 2 since fl,ow indication is not available. 4 3. This pump uses water lubricated bearings and thus lubrication-level and 1 bearing temperature measurements cannot be taken. 4. These pumps are not equipped with recirculation / test lines. The nature _( of theisystem they feed makes it impossible to specify a particular flow-j path that can always be repeated. Various components which they feed will j sometimes require cooling water and sometimes not. Sequoyah will initially j establish an in situ pump curve which establishes the relationship between 1 (- . flow and differential pressure in a band around the pump design point. F Subsequent inservice tests would then compare test data to this curve using- ~ l the allowable test ranges per IWP3210. 5. The pump bearings are inaccessible as the pump is submerged in a pit. 6. These pumps have no installed instrumentation to measure bearing tecperature. . i I 1 7. The Auxiliary ERCW pumps are only required for Sequoyah Unit 1. Section XI testint requirements will be deleted when Sequoyah's Technical Specifications are revised to ' delete those pumps. ' 8. 9 Vibration amplitude cannot be measured to the + 5% accuracy required. The "out of tolerance" accuracy of the Licensee vibration test equipment shall be i 11%. i i 4 { i n A-3

a s (- t 3 -I j.. j APPENDIX B EXPLANATION OF CODES AND SYMBOLS USED IN THE SEQUOYAH VALVE INSERVICE TESTING PROGRAM L .This Appendix defines the meaning of all codes and symbols used in the valve test program presented in Appendix C. t e i O b t -{.: e O i t 4-a ~ ~ . B-1

l s i l SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 POMP AND VALVE { INSERVICE TESTING PROGRAM k Submitted: ?/3/82 Y Date y i { l s t 1 I, e 9 4 I 8203090382 820303 ,. PDR ADOCK 05000327 {* p PDR

TABLE OF CONTENTS 4 f Section Title Page i t j

1.0 INTRODUCTION

1 i 2.0 PUMP INSERVICE TESTING PR0 GRAM............................. 1 2.1 PUMP TESTING FREQUENCY..................................... 1 3.0 VALVE INSERVICE TESTING PR0 GRAM............................ 2 3.1 CATEGORY A VALVES.......................................... 2 8 t 3.2 THERMAL RELIEF VALVES...................................... 2 3.3 THERMAL RELIEF CHECK VALVES................................ -3 3.4 CORRECTIVE ACTI0N.......................................... 3 3.5 SYSTEMS OUT OF SERVICE..................................... 3 3.6 EMERGENCY DIESEL SYSTEMS................................... 3 Jp. 3.7 FAIL-SAFE ACTUATORS........................................ 4 h 3.8 6; VALVE TIMING AND REMOTE INDICATION......................... 4 I: o 3.9 PASSIVE VALVE.............................................. 4 1 3.10 COLD SHUTDOWN TESTING...................................... 4 4 APPENDIX A................................................. A-1 APPENDIX B................................................. B-1 3 ,f APPENDIX C................................................. C-1 t' 51 APPENDIX D................................................. D-1 I e O j r ,n -g ~, -,.n-,

= s 4 4 APPENDIX A SEQUOYAH PUMP INL,ERVICE TESTING PROGRAM I Summarv of Information Provided l The pump test table (Table A) provides the following information on testing requirements: j 1. System Drawingonwhichthepumph.sdepicted 2. +

j 3.

Speed 4 4. Inlet Pressure ~ ~ 5. Differential Pressure 6. Flow Rate i i .7. Vibration Amplitude 8. Observation of Lube Oil Leval/ Pressure i 9. Bearing Temperature 1 .i

  • l I

0 J o9 i A-1 .,,, - - -. _ _ _, _ ~,.

4 SEQUOYAH NUCLEAR POWER PLANT TABLE A--PUMP TEST PROGRAM Drawing Inlet Differential Fl o.' Vibration Bearing Observe Lube Oil 0 Pump Nurber Speed Pressure Pressure Rate Amplitude Temperature Level / Pressure _ n P AP Q V T g b Auxiliary Feed 47W803-2 Note 1 Q Q Note 2 Q Note 6 Yes Water (Motor) Auxiliary Feed 47WS03-2 Q Q Q Note 2 Q Note 6 Yes Water (Steam) Centrifugal 47W811-1 Note 1 Q Q Note 2 Q Q Yes Charging 47W809-1 y Safety Injection 47W811-1 Note 1 Q Q Q Q Q Yes System N Essential Raw 47W845-5 Note 1 Q Note 4 Note 4 Note 5 Note 6 Note 3 Cooling Water Auxiliary Essential 45W845-1 Note 1 Q Note 4 Note 4 Note 5 Note 6 Note 3 Raw Coolant Water Note 7 Component Cooling 47W859-1 Note 1 Q Note 4 Note 4 Q Note 6 Yes Containment Spray 47W812-1 Note 1 Q Q Q Q Note 6 Yes Residual Heat 47W810-1 Note 1 Q' Q. Q Q Note 6 Yes Reepval e s O

i f 3 j

p t 4 1

} } NOTES t i 1. Synchronous or induction motor driven pumps do not require speed check per } IWP-4400. i l 2. Flow rate is not required since this pump is tested in a fixed resistance j pathway. Relief is requested from the 1977 Edition through Summer 1978 Addenda for Unit 2 since fl,ow indication is not available. - i 3. This pump uses water lubricated bearings and thus lubrication level and bearing temperature measurements cannot be taken. 4. These pumps are not equipped with recirculation / test lines. The nature of the system they feed makes it impossible to specify a particular flow { path that can always be repeated. Various components which they feed will j sometimes require cooling water and sometimes not. Sequoyah will initially i establish an in situ pump curve which establishes the relationship between i flow and differential pressure in a band around the pump design point. L Subsequent inservice tests would then compare test data t'b' this curve using the allowable test ranges per IWP3210. The pump bearings are inaccessible as the pump is submerged in a pit. 5. 6. These pumps have no installed instrumentation to measure bearing tecperature. 7. The Auxiliary ERCW pumps are only required for Sequoyah Unit 1. Section XI testing requirey.ents will be deleted when Sequoyah's Technical Specifications are revised to delete those pumps. 8. Vibraticn amplitude cannot be measured to the + 5% accuracy required. The "out of tolerance" accuracy of the Licensee vibration test equipment shall be 11%. I i i 4 b r a A-3

i i = 4 [1 .? 'V

A.

!I I.

j' APPENDIX B f

i d 1 ; EXPLANATION OF CODES AND SYMBOLS USED IN , y' THE SEQUOYAH VALVE INSERVICE TESTING PROGRAM I< I s This Appendix defines the meaning of all codes and symbols used in the valve j test program presented in Appetidix C. t i II 4 i i.! t 's A {' ? ~ i' 4 i i 1 i i i t j l 3 1 i 4 i i A l l i 11 1 f-B-1

i I o i ,i .1 l l' t 1 9 -3 ]-l TABLE B-1 4 ~.;. ! 3 SYMBOLS USED TO DESIGNATE VALVE TYPE i 1' 4 VALV'E TYPES rf. SYMBOL Meaning d BUT Butterfly BAL Ball CK Check {h DIA Diaphragm GA Gate i GL Globe '~ ji ND Needle i AN , Angle

.i PLG Plug l -l-RD Rupture Disk l 1 REL.

Relief ll SC Stop Check l SK Spring Check 1 i1 t 4 l j i B-2

s 5 I i. ? TABLE B-2 i j SYMBOLS USED TO DESIGNATE VALVE ACTUATOR TYPE VALVE ACTUATOR TYPES 4 SYMBOL Meaning }l['j DIA Diaphragm Air Operator I M Manual Operator 4 M0 Motor Operator j f SA Self Actuated j SO Solenoid Operator CYL Cylinder / Hydraulic Operator i RD Rupture Disc 1 4 9 B-3

5 l Y, 3 4 l TABLE B-3 I: SYMEOLS USED TO DESIGNATE VALVE POSITION l! g VALVE POSITIONS

j SYMBOL Meaning 1

'I } O Open C Closed i LO Locked Open I LC Locked Closed Til Throttled Valve position determined by other system paraceters as in the case of any check valve. 3 B-4

a r TABLE B-4 [ SYMBOLS USED TO DESIGNATE TESTING REQUIREMENT i CATEGORY A OR B VALVES 1 ij QT-1 Exercise valve (full stroke) for operability every 3 months, in accordance with Section XI, Article IWV-3411. L f). QT-2 Exercise valve (part stroke) for operability every 3 months and full stroke at cold shutdewn, in accordance with Section XI, Article IWV-3412(a). ~ } CS These valves have been specifically identified in Appendix D as valves which cannot be tested during power operation. These valves shall be full stroke tested during cold shutdcwns only, in accordance with Section X1, Article IWV-3412(a). SLT Perform a Seat Leak Test during refueling, but not less than once every 2 years. Leak rate limits will be established by the licensee in accordance with 10CFR50 Appendix J. f SLTP Perform a Seat Leak Test for pressure isolation function as required by Technical Specifications. ER Exercise full stroke at refueling only. I t B-5

T s 1 l i i ? L [i 'I TABLE B-4 (continued) hi l ~; SYMBOLS USED TO DESIGNATE TESTING REQUIREMENT ls Ft ,{ CATECORY C VALVES 4 I-CV-1 Exercise valve (full stroke) for operability every 3. months, I" in accordance with Section XI, Article IWV-3520. it} CV-2 Exercise. valve (part stroke) for operability every 3 months and full stroke at cold shutdown, in accordance with Section XI, Article IWV-3520. 1 CS These valves have been specifically identified in Appendix D as i. valves which cannot be tested during power-operation. These 'j. valves shall be full stroke tested during cold shutdown only, in accordance with Section XI, Article IWV-3520. + I. i SLT Perform a Seat Leak Test during refueling, but not less than I once every 2 years. Leak rate limits will be established by the 1 licensee in accordance with 10CFR50 Appendix J. 4 SLTP Perform a Seat Leak Test for pressure inolation function as required by. Technical Specifications. i. fI RF Test safety and relief valve setpoints in accordance with-L - Section XI, Article IWV-3510. ER Exercise at refueling only. i 3 T i B-6

.._.~._. 1.i 1 a t -c f' i ? E a e I TABLE B-4 (continued) g ) SYMBOLS USED TO DESIGNATE TESTING REQUIREMENT l 1 .i ,- o ? CATECORY D

s RD Operational checks of rupture discs shall be performed in-h accordance with the manufacturers' recommendations. The frequency of tests shall be specified by the-licensee -in j

accordance with Section XI, ' Article IW-3620. ~I

[.,

~ s e t 1. ) f t l 4 g. 4 4 4 4 e 4 g B-7 ~ ' 'y a*f ew,s1y r "y y e-y v: +?y-r-- = c ae w -t--s-7e yv-w rtre se--+*e1 w- -gy.-se = r. s-- -p r g e gy-wtm e-- sy ve ev e a-ee i - tr-s---&

I: -D U b i h

  • 2 E

d E ,k APPENDIX C t f SEQUOYAH NUCLEAR PLANT VALVE PROCRAM N }l Summary of Information Provided V I The following Tables use the format referenced-in the '1978 "NRC Staff g Cuidance for Preparing Pump and Valve Test Program Descriptions and Associated Relief Requests Purs'uant to 10CFR50.55a(g)" to give valve descriptions. The following information is provided: e ~ L 1. System Name and Number I 2. Drawing Number g ii 3. Valve Number h 2 4. ASME Section XI Classification .I . j 5. Drawing Coordinates of Valve j w. f 6. Valve Category Per Section XI, Article IWV-2110 1 7. Valve Sice s i

  • i 8.

Valve Type t 9. Actuator Type 10. Normal Position 4 11. Testing Required Per Section XI I 12. Relief Request Required 13. Alternate Testing 14. Remarks (Including Relief Request Numbers, Specific Valve Data, etc.) Note: Tests of the following valves will be deleted when the technical specifi-cation requirement of the AERCW system is deleted since they will be B-Passive ) or C-Passive. ~ FCV-67-12 FCV-67-367 FCV-67-14 656A FCV-67-360, 361, 362 656B 363, 364, 365, 366 669A, 67-669B C-1

O Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (1) MATN STFA'f ~ DRAWING NO: _47W801-1 (R18) E S UH >4 H 0 VALVE wy U$ 9 $a $w O TESTING by $U u [$ j <0 U d$ h REQUIRED U $ id $ RDtARKS NUMBER og h 0 8 N M hN U O A ec FCV-1-4 -2 C-4 IB-ACT 32 GA cyL 0 QT-2 MSIV FCV-1-11 2 E-4 R-ACT 32 GA

cit, O

QT-2 MSIV FCV-1-22 2 G-4 B-ACT 32 CA CYL 0 QT-2 MSIV FCV-1-20 2 A-4 B-ACT 32 CA CYL 0 QT-2 uc:TV FCV-1-147 2 C-4 B-ACT _2 GL DIA C QT-1 FCV-1-148 ? E-4 g-ACT 2 GL DIA C QT-1 FCV-1-149 2 G-4 B-ACT 2 GL DIA C QT-1 FCV-1-150 2 Ad B-ACT 2 GL DTA C OT-1 FCV-1-5 2 C-2 9ACT 6 GA DIA C CS* Cycled BC PCV-1-12 2 D-2 -ACT 6 CA DIA C CS* cveled BC PCV-1-23 2 F-2 -ACT 6 GA DIA C CS* Cveled FCV-1-30 2 A-2 ACT 6 CA ' DIA C CS* Cycled 1-512 2 F-3 C 6 REL SA C RF 1-513 2 F-3 C 6 REL SA C RF 1-514 2 F1 C 6 REL SA C RF 1-sis 2 F-3 C 6 REL SA C RF 1-516 2 F-3 c 6 REL SA C RF 1-517 2 D-3 C 6 REL SA C RF 8 C-]A

= Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (1) MAIN AND RFHFAf FTFAM DRAWING NO: 47W801-1 (RIS) n W ee n: -o TESTING [3 b yU hO VAbYE g$ O D.1 W W ea WR 40 L "D RzeuIRED 3s kB; nEnARxS

  • ~

nunnER as de 8e e o ww =8 gW B" "8 6 U A l 1-518 -2 D-3 C 6 REL SA C RF l 1-51o 2 D-3 C 6 REL SA C RF 1-520 2 D-3 C 6 REL SA C RF 1-521 2 D-3 C 6 R ET. SA C RF 1-522 2 C-3 C 6 REL SA C RF 1-523 2 C-3 C 6 REL SA C RF 1-524 2 C-3 C 6 REL SA C RF 1-5?5 2 C-3 C 6 REL SA C RF 1-526 2 C-3 C 6 REL SA C RF 1-527 2 A-3 C 5 REL SA C RF 1-528 2 A-3 C 6 REL SA C RF 1-5?o 2 A-3 C 6 REL SA C RF 1-530 2 A_3 C 6 REL SA C RF 1-531 2 A-3 C 6 RFL SA C RF C-2

Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (1) STF nf CENFPATOD'NTOtmOIN DRAWING NO: 47W801'-2 (R14) a e OH N N g He l ~ VALVE gy dN $w Nw hO TESTING $m hN w NUMBER Gj O N d$

  1. $ 25 REQUIRED U

id $ REMARKS l Ag h Oh N U o A FCV-1-181 ? C-2 B-ACT ? CL DIA O QT-1 i FCV-1 -18 2 9 F-2 B-ACT 2 CL DIA O OT-1 1 FrV-1-1P1 2 F-2 B-ACT 2 CL DIA O OT-1 l Fev-1-184 2 B-2 B-ACT 2 GL DIA O OT-1 FCV-1-7 2 C-3 B-ACT 2 AN DIA O OT-1 FCV-1-14 2 E-3 B-ACT 2 AN DTA O OT-1 FCV-3-25 ? F-3 B-ACT 2 AN DIA O OT-1 I B3 B-ACT 2 AN DTA O QT-1 FCV-1-32 2 er k C-3

___._m........... c . 66 s Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (M FFmWATFR DRAWING NO: 47W803-1 (R12) 0 S 06 N CC H O U$ TESTING D b hU $w @w jU VALVE m a w NUMBER dO N d$ T2 5 REQUIRED U id $ REMARKS b M >b h6 H O O= 8 d W S" b NW 8 6 W O A yfy 1 11 -2 C-3 B-ACT 18 GA ID 0 CS* FrV-3-47 2 E-3 R-ACT 18 CA 3p 0 CS* FCV-3-87 ? C-3 B-ACT 18 cA 10 0 CS* FCV-3-100 2 B-3 B-ACT 18 GA ID o CS* 3-908 2 G-2 C 16 CK SA CV-1 X See PV-8 3-509 2 E-2 c 16 CK SA CV-1 X See PV-8 3-510 2 C-2 C 16 CK SA CV-1 X See PV-8 3-511 2 B-5 C 16 CK SA CV-1 X See PV-8 C-4

= Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (3) APXILT ARY FEEWATER DRAWING NO: _47W80%2 (Rio) O oH m H o g U$ n 9 VALVE M $u Ow dO TESTING DM hU w Gh NO U d$ 4$ h5 F2 QUIRED U sd$ REMARKS NUMBER U Qg N N u C-3-810 3 G-4 C 10 CK 'SA CV-1 X Yes See PV-9, Puen Test %820 1 F-5 C 6 CK SA CV-1 X See PV 6 l CK 3-821 1 F-6 e SA CV-1 X See PV-12 3-830 2 Fo e 4 ! CK SA CV-1 X See PV-12 1-911 2 Eo c 4 CK SA rV_1 X See PV-12 3-832 2 ro C 4 CK SA CV-1 X See PV-12 3-833 ? A-9 C 4 CK SA CV-1 X See PV-12 %AA1 2 F-10 C 4 CK SA CV-1 X See PV-12 3-862 2 F-1n C 4 CK SA CV-1 X See PV-12 1-FA4 3 G-6 C 6 CK SA CV-1 X See PV-12 3-A71 2 F-o C 4 CK SA CV-1 X See PV-12 1-872 2 00 C 4 CK SA CV-1 y See PV-12 3-R73 o C-9 c 4 CK SA CV-1 X See PV-12 3-874 2 A_o C 4 cv SA ev-1 y See PV-12 % 841 3 p-9 C 4 cr SA CV-1 X Ye.:. See PV-9, Pump Test 1-909 3 A-8 C 4 CK SA CV-1 y Yes See py o. Pn p Test 3 021 2 G-In C 4 cv 93 rV-1 X See PV-12 3-922 2 E-10 C 4 rK SA CV-1 X See PV-12 s C-5

j m... _. - m Sequoyah Nuclear Plant inservice Valve Testing Program t I k SYSTEM: (3) AUXILIARY FEEDWATER 4 DRAWI?JG 110: 47W803-2 (R19) i l N N I OH H N H O VAI,VE gy U E! $w 0w jh ~ g D hU o n2 TESTIfiG U @y id $ REMARKS I; UMBER Ci j ,:: O N d$ @d', h 'H REQUIRED 4 0 M >b b Mg y ogu A i 3-814 -3 F-5 C 115 CK SA C CV-1 Pump Test 3-915 3 F-6 C 184 CK SA C CV-1 Pump' Test - 3-818 3 G-7 C l'd CK SA CV-1 Pump Test t l 1, 1 I ) ? i t l 0 I y I f( at t' C-6

2 __ Sequoyah Nuclear Plant inservice Valve Testing Prograra SYSTEM: (3) AUXILIARY FEEDUATER ~ DRAWING NO: 47W803-2 (R19) OH >4 n; H 0 g U$ $w 8w Qh TESTING VAINE M $p yM w U *y NUMBER 6i j [# O U .i $ h 5" $! "H REQUIRED o'!$ RMARKS D 6 0"8 M M B" WW "8 6 4 O A LCV-3-171 '3 A-8 ll-ACT 4 GL DIA C QT-1 ICV-3-171A 3 E-8 B-A CT 2 CA DIA C OT-1 Cveled T.CV 17 2 a F-8 B-ACT 3 GL DIA C QT-1 Cycled TFV-1-171 1 D-8 B-ACT 3 GL DIA C OT-1 Cveled TCV-3-174 3 C-8 B-ACT 3 GL DIA C QT-1 Cycled TCV-3-175 1 A-8 B-ACT 3 GL DTA C QT-1 cveled 3-805 3 F-5 C 8 CK SA C CV-1 X Yes See PV-4 Pump Tect 3-806 3 Fk C 8 CK SA C CV-1 X Von See PV-9. Pumn Test FCV-3-116A 3 F-6 B-ACT 8 CA MO C QT-1 FCV-3-116B 3 F-6 B-ACT 8 GA FO C OT-1 FCV-3-176A 3 F-7 B-ACT 8 CA Fh C OT-1 FCV-3-126B 3 F-7 B-ACT 8 CA Fh C OT-1 FCV-3-136A 1 G-5 B-ACT 10 CA Fn C OT-1 FFV-1-116n 3 G-5 B-ACT 10 CA Fh G OT-1 FrV-1-170A 3 G-5 B-ACT in GA FD C OT-1 rev q_170B 3 G-5 B-ACT in GA FD C OT-1 TrV-1-14A 3 F-8 R art 4 GA DIA C QT-1 ICV-3-14PA 3 F-A B-ACT 2 CA DTA C OT-1 Cycled t C-7

.~ Sequoyah Nuclear Plant Inservice Valve Testing Program SYSTEM: (3) AtiXTLTARY FEEDWATER DRAWING NO: 47W803-I2 (R19) { i N Y 08 CG H 0 VALVE gy U E$ $o P kU w w g w TESTING D yU rk " Nw N [d 5 REQUIRED U$ [d N REMARKS ? NUMBER iji j k >P U2 >b E4 e oH gO 4o Mw 8 W B" "8 6 8 u A T.CV-3-156 3 E-8 R-ACT 4 CA DIA C QT-1 I.CV-3-156A 1 E-8 B-ACT 2 CA DTA C OT-1 Cycled T CV-3-164 3 C-8 3-ACT 4 CA DIA C OT-1 TCV-3-164A 1 C-8 3-ACT 2 GA DIA C OT-] Cycled FCV-1-15 9 B0 9-ACT 4 GA MO O QT-1 hw FCV-1-16 2 A-9 3-ACT 4 GA MC 0 QT-1 FC'7 17 3 B-8 3-ACT 4 CA MO O cs* FCV-1-18 3 B-8 B-ACT 4' GA MO O CS* PCV-3-122 3 F-5 B-ACT 4 CA DTA O OT-1 Cveled PCV-3-132 3 F-6 3-ACT 4 GA DIA O QT-1 Cvcled l 1 l l s C-8

............m Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (26) FTPF PROTECTION DRAWIt;G 1;O: 47k'850'--10 0 oa ct: so g dN $ta O ca kO S{ b VALVE M y$U ra TESTI!;G Li h 4O N d$ REQUIRED U !.' UMBER N . REMARKS Ag h O Nk h$ U o O 4 g FCV-26-243 -2 3-1 4 CA MO O QT-1, SLT ,3-ACT m-26-1296 2 B-3 -PAS 4 CK SA SLT FCV-26-240 2 A-9 A-ACT 4 CA MO O QT-1, SLT AG-2A-1?An 2 A-Q PAS 4 CK SA SLT FCV-26-241 3 D-7 B-ACT 4 CA MO O QT-1 242 3 D-i B-ACT 4 CA MO O QT-1 244 3 C-2 B-ACT 4 CA MO O QT-1 245 3 C-1 B-ACT 4 CA MO O QT-1 h e e C-9

.. m..,.-- .. _. m._..m...._ m Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: ( !n) UFATINC ANir VFt'TTI.ATING AIR FLOW DRAWING MO: 47K866'-1 (R23') E 0P W (4 H 0 VALVE gy d$ $w @w %6 TESTING hU w [jn. O" l O N d$ is $ [;! "N REQUIRED U o! $ REMARKS NUMBER si,'j et u >H U2 >H H o (4 O ww "8 6 " El M U" u A ,c FCV-30 7 2 C-1 .\\-ACT 24 BUT CYL C QT-1, SLT FCV-10-8 2 C-2 \\-ACT 24 BUT CYL C QT-1, SLT FCV-10-0 2 C-1 A-ACT 24 BUT CYL C QT-1, SLT Frv 70-10 ? E-? T-art 24 BUT CYL C OT-1. ST.T FCV 10-14 2 F-1 A-art ?4 BIT CYL C OT-1. STT FCV 10-1; 2 F-2 A-ACT 24 Birt CYL C OT-1, SLT FCV-10-16 2 F-1 A-ACT 24 BUT CYL C QT-1, SLT FCV-10-17 2 F-?' ,\\-ACT 24 EUT CYL C QT-1, SLT FCV-10-14 2 C-1 A-ACT 24 BUT CYL C QT-1, SLT FCV-10-20 2 G-2 A-ACT 24 BUT CYL C QT-1, SLT FCV-3n-37 2 D-10 A-ACT 10 EUT CYL C OT-1, SLT rCV '0-60 ? 0-9 A-ACT 10 Btrr ' CYL C OT-1. ST T rCV-30-50 2 C-10 A-ACT 24 BUT CYL C QT-1, SLT FCV-30-51 2 C-lO A-ACT 24 BUT CYL C QT-1, SLT FCV-30-92 2 C-10 A-ACT 24 BliT CYL C QT-1, SLT FCV-10-53 2 C-10 A-ACT 24 BUT CYL C QT-1, SLT FCV-30-56 ? F-9 .\\-ACT 24 BUT CYL C QT-1, SLT FCV-30-57 2 E-10 \\-ACT 24 BUT CYL C QT-1, SLT Y C-30

Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (70) FF ATI!!C. ANTY VENTILATING AIR FLOW DRAWING NO: 47W866-1(R23) U N ee m -o p TESTING ['] b yU VALVE gy 3$ $g 8y j6 >4 0 y d$ 4@ g5 REQUIRED U S Id S REMARKS NUMBER (fj j da = de Ee o~ o < u p ww 8 o X "8 EM us O A vry 70 48 "9 Co A-ACT 12 BUT CYL 0 OT-1, SLT FCV-30-54 2 G-10 A-ACT 12 BUT CYL 0 QT-1, SLT FCV-30-46 7 B-4 A-ACT 20 BUT CYL 0 QT-1, SLT FCV 10-47 ? B-5 A-ACT 20 BUT CYL 0 QT-1, SLT FCV-30-48 2 B-7 A-AC 20 BUT CYL 0 QT-1, SLT FSV-30-134 2 F-9 A-ACT 3/8 CA SO O QT-1, SLT i FSV-30-135 2 F-9 A-ACT 3/8 GA SO O QT-1. SLT 10-971 7 F-4 ACACT 20

RET, SA C

RF SLT 30-372 2 B-5 ACACT 20 REL SA C RF SLT 30-573 2 B-7 ACACT 20 REL SA C RF SLT 1 i I 6 I a c-1)

g Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (113 A T Y? PO"nTTT'ONTNG CllTT T,FT1 UATEP DRAWING 130: 47W865'-5 0H N D: H O y 5$ $g @g jU TESTI!IG Sj b yU VALVE g tiUMBER mj % "q gO O d$ d$ 2 E* REQUIRED U $ N$ NA H W >b O g O REMARKS 4 0 bb =g Ag ge "8 >6 H gy U 4 g FCV-3]C-??? '2 A-7 .\\-ACT 2 CA DIA 0 QT-1, SLT FCV-31C-223 2 A-8 \\-ACT 2 CA DIA O QT-1, SLT FCV-31C-224 2 B-7 1-ACT 2 GA LIA 0 QT-1, SLT Fev-11 C -? ? ; 2 B-8

\\-ACT 2

GA DIA O QT-1. SLT rev-11r 990 9 D-7 i ACT ? CA DTA O OT-1. ST.T FCV-31C-210 2 D-8 .\\-ACT 2 CA DIA O QT-1, SLT FCV-31C-231 2 E-7 A-ACT 2 GA DIA O QT-1, SLT FCV-31C-21? 2 E-8 A-ACT 2 CA DIA O QT-1, SLT AC-31C-752 2 B-8 PAS h SK SA C SLT TRCV AC-110-734 2 C-R PAS 4 SK SA C SLT TRCV AC-11C-715 2 E-8 PAS 4 SK SA C SLT TRCV 11C-647 2 F-8 PAS h SK SA C SLT TRCV l i W C-12

m = Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (12) COMPRFSSFD ATR DRAWIf3G 110: 47W84811 (R13) N 0e e t4 H O VALVE M qU TESTI!1G hb $U $w O w w J[* f"2NO N d$ IJUMBER g$ k "5 REQUIRED U id $ REMARKS m<o >e m >e "8 go e o mm "8 6 N us .c U A FCV-32-80 2 C-9 A-ACT 2 CA DIA 0 CS*, SLT FCV-32-102 2 D-9 A-ACT 2 GA DIA 0 CS*, SLT FCV-32-110 2 A-9 A-ACT 2 CA DIA 0 CS*, SLT AC-32-287 2 A-10 ACT 2 CK SA CS*, SLT AC-32-207 2 C-10 ACT 2 CK SA CS*, SLT AC-32-377 2 D-10 ACT 2 CK SA CS*. SLT 17-175 2 B-9 A-PAS 2 GA M C SLT 32-285 2 C-4 A-PAS 2 CA M C SLT 32-295 2 E-9 A-PAS 2 GA M C SLT FCV-32-81 2 F-9 A-ACT 2 CA DTA 0 CS*, SLT FCV-32-103 2 E-9 A-ACT 2 GA DTA 0 CS*, SLT FCV-32-lll 2 C-9 A-ACT 2 CA DTA 0 CS*, SLT l l Y C-13

2L Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (32) COMPRESSED ATR DRMING NO: 47W848-1 (Rl.0 0 0t ' lH N H 0 VAI,VE ga y U {$ $ga O ga kU TESTING Db hU ni IRJMBER [l} j gO [$ d$ [2 N REQUIRED U h! $ REMARKS u M >b H Q y ag U N 32-348 ~7 E-10 iC-ACT ' 2 CK ~SA CS*, SLT 358 2 F-10 iC-ACT 2 CK SA C S*. ST.T 387 2 G-10 iC-ACT 2 CK SA CS*, SLT 341 2 E-9 A-Pas 2 CA M C SLT 353 2 F-9 A-Pas 2 CA M C ST.T 385 2 G-9 A-Pas 2 CA M C ST.T l s e 4 / C-14 I

_ _ _.. ~ 2 = Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (33) CONTROL & SERVICE AIR - DRAWIt!G 110: 47W846-2 (R18) U 06 N M H O qy U !! $w Ow kh ~ VALVE g dy hd w TESTIFIG IRIMBER [ "q U Q REQUIRED ]r REMARKS w "8 6 "8 M U" O A 4 33-704 '2 F-7 A-PAS 2 DIA M C SLT 33-740 2 F-6 A-PAS 2 GA M C SLT 33-722 2 F-4 A-PAS 2 DIA M C SLT 33-739 2 F-4 A-PAS 2 GA M C SLT ~ 9 e n. 4 C-15

m .....--.---.. ~ y. Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (43) SAMPLING ^' ~ DRAWI!1G 110: 47k'625-1 (R15) E 0H H N H 0 VALVE gy U$ $o $ ra Ow ,j U TESTI!JG Db yU ra rJUMBER Gj dO N d$ @k N REQUIRED US NN REMARKS o M >b b Q y ag U A et rev-41-9 -2 C_-4 A-ACT 3/8 CA DIA O QT-1, SLT _FCV-43-3 ? C-5 .\\-ACT 3/8 CA DIA o QT-1, SLT FCV-43-11 2 c-4 A-/CT 3/8 GA DIA C. QT-1, SLT FCV-43-12 2 C-5 A-ACT 3/8 CA DTA C QT-1, SLT FCV-41-22 2 F-5 A-ACT 3/8 CA DIA O QT-1, SLT FCV-43-23 2 D-5 A-ACT 3/8 CA DIA O QT-1, SLT g 4 C-16

Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (43) SAMPLING DRAWING NO:, 4 7k'6 ? s-? (R11) U 0 E4 0: H o gj U$ $w 8w dO TESTING D yU VALVE M y NUMBER N NO U N$

  • ! $ hU IEQUIRED U$

!d t$ REMARKS U Rg O N U N FCV-43-34 ? C-2 \\-ACT 3/8 CA DTA C QT-J, SLT FCV-43-35 ? C-3 A-ACT 1/8 CA DIA C QT-1, SLT FCV-43-;. 3 C-8 B-ACT 3/8 CA DIA 0 OT-1 FCV-43-58 3 C-8 B-ACT 3/8 CA DIA 0 QT-1 FCV-43-61 1 C-8 B-ACT 1/8 CA DIA 0 OT-1 FCV-43-64 3 D-8 B-ACT 3/8 CA DIA 0 QT-1 8 e W C-17 G

a Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (43) SAMPLING - DRAWI!1G 110: 47k'625-7 (R13) E s 0b >+ C4 H 0 $w @w QU TESTI!JG $1 b hU g U$ VALVE m p3 !1 UMBER [jj f" NO [j ,i $ b'< $ ~2 "N REQUIRED U id$ REMARKS B B 0 0 8 >6 ,1 =8 dD d' de NN o A pcy-43-75 -2 D-6 A-ACT 3/8 CA DIA C QT-1, SLT FCV-43-77 2 D-7 A-ACT 3/8 CA DIA C QT-1, SLT 9 e M C-38

.. _. - -..., __.. a......=.,n....,,,,.......,, .. n w - m.s Sequoyah Nuclear Plant Inservice Valve Testing Program SYSTEM: (43) SAMPLING ~ DRAWING NO: 47W625-Il (R9) l 0 W 08 N a: wo VALVE gy 5y ygg Q ra [k ~ U TESTING b U 2 U REQUIRED U$ y$ a ga NUM3CR di j gd y Q@ h@ TJ REMARKS p e oH gO u >s ra ta g8 a M de ~ o U 4 g FCV-43-201 9 F-8 ,\\-ACT 3/8 GA DIA 0 QT-1, SLT FCV-43-202 2 C-9 A-ACT 3/8 GA DTA 0 QT-1, SLT FCV-43-207 2 C-10 A-ACT 3/8 GA DIA 0 OT-1. SLT FCV-43-208 2 B-11 A-ACT 3/8 GA DIA 0 QT-1, SLT t t 8 C-19

a Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (59) DEMINERALIZED WATER 6 CASK DECONTAMINATION DRAWING no: g wpsg_3 (93o3 m M w os N m H o $w 0m d~ TESTIt3G !Il y hU gg 5@ p VALVE m O w hh h Nd U d$ !$ $ h5 REQUIRED UD M$ RE*! ARKS NUMBER 4o M >b H g Mg ag o A At.;- c o_ g p 2 F-3 PAS ~2 CK SA SLT 50-5?? o F-3 A-PAS 2 G; M I.C 91 T 59-529 2 F-3 A-PAS 3/4 BUT M 0 SLT O h e p C-20

n Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (61) ICE CONDENSER' DRAWItJG r;O: 47W814'2 (F13) U U oe u m g d {$ 8y q' b so VALVE M g a 6 TESTIt;G d yN tiUMBER Gj m%$ NO N D R e$ $ REQUIRED U$ N$ REMARK" N 4 <o m >e m o-a "8 0 W "8 du M $3 ww U 4 g FCV-61-192 2 A-5 A-ACT 4 DIA DIA 0 QT-1, SLT vrv-A1-lo1 2 A-5 A-ACT 4 DIA DIA 0 QT-1, SLT AC 61-533 2 A-5 PAS 3/8 SK SA C SLT TRCV FCV-61-191 2 A-5 A-ACT 4 DIA DIA O QT-1, SLT FCV-61-194 2 A-5 A-ACT 4 DTA DIA O QT-1, SLT AC-61-680 2 A-5 PAS 3/8 SK SA C SLT TECV FCV-61-96 2 C-10 A-ACT 2 DIA DIA O QT-1, SLT FCV-61-97 2 C-10 A-ACT 2 DIA DIA O OT-1. SLT AG-61-692 2 G-10 pas 3/8 SK SA C SLT TRCV FCV-61-110 2 H-10 A-ACT 2 DTA DTA O QT-1, SLT FCV-61-122 2 H-10 A-ACT 2 DIA DIA O OT-1, SLT 61-745 2 H-lO ^ PAS 3/8 SK ' SA C SLT TRCV k C-21

Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (62) CIIEMICAL & VOLUME CONTROL SYSTEM DRAWING 110: 4 7W809'-1 (R19) E S OH N H O gg U$ VALVE 9 $a Ow kU TESTING dy [h M w NUMBER ij N O" NO O N$ 2' "N REQUIRED Ug d$ REMARKS 4o >H t/2 >b b O "8 6 J "8

p M B"

WW o S FCV-62-72 2 A-5 A-ACT 2 GL DIA C QT-1, SLT FCV-62-73 2 A-4 A-ACT 2 CL DIA 0 QT-1, SLT FCV-62-74 2 A-4 A-ACT 2 GL DIA C QT-1, SLT FCV-62-77 2 A-7 A-ACT 2 GL DIA 0 QT-1, SLT FCV-62-90 2 D-7 B-ACT 3 CA M0 O QT-1 FCV-62-41 2 D-8 E-ACT 3 CA M0 O QT-1 FCV-62-48 3 D-9 B-ACT 2 CA MO O CS* FCV-62-44 3 D4 B-ACT 2 GA M0 O CS* T"V-6?-135 2 11 - 1 0 B-ACT 8 GA M0 C CS* LCV-62-136 2 11-10 B-ACI 8 GA M0 C CS* FCV-62-61 2 B-7 A-ACT 4 GA MO O CS*, SLT FCV-62-63 2 B-8 A-AC1 4 GL MO O CS*, SLT FCV-62-132 2 E-10 B-ACT 4 CA MO O CS* FCV-62-133 2 E-10 B-ACT 4 GA MO O CS* 6?-514 2 F-9 C-PAS 3 CK SA C None Punn Test 62-525 2 H-9 C 4 CK SA C CV-1 X ER See PV-1. Pump Test 62-532 2 C-9 C 4 CK SA C CV-1 X ER See PV-1, Pump Test 62-644 2 C-9 C 2 REL SA C RF k C-22

2 = e Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (62) CHEMICAL & VOLUME CONTROL DRAWING no: 47W809-1 (R19) N De N N HO gy dy o" ~ $ta O ga fU TESTING Db yU VALVE ra NUMBER Gj a%y 40 y >d ": b@ Q "$ REQUIRED U "$ N$ REMARKS 'y i 4 0 m >e m " "8 W W S" e" 8 0 U AC-62 662 ~2 A-3 ACT 2 REL SA C RF, SLT A'-675 2 A-10 C 2 REL SA C RF 62-636 2 B-6 C 2 REL SA C RF 62-504 2 H-10 C 8 CK SA CV-' X ER See PV-2 62-639 2 C-7 iIS 3/4 SK SA SLT (TRCV) 62-523 2 H-9 C 2 CK SA CV-1 Pump Test 62-530 2 G-9 C 2 CK SA CV-1 Pump Test 62-607 2 E-ir C-ACT 4 CK SA CV-1 Pump Test e M k C-23

a Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (61T R AFFTV TN TfCTION SYSTFM DRAWING NO: 47W811-1 (R20) 0 dnoy cc so $g 8y QU TESTING $b ,] U VALVE gy w MBER f EQUIED U PEMARKS as 6 a =a W N ns U N 4 FCV-61-8 '2 11 - 9 B-ACT 8 GA MO C CS* FrV-61-71 H-6 B-AC1 18 GA MO C CS* FCV-63-11 2 F-9 B-ACT 8 GA M0 C CS* FCV-63-41 2 A-9 B-AC1 1 GL DIA 0 QT-1 FCV-63-42 2 A-9 B-AC3 1 G7 DIA 0 QT-1 FCV-63-39 2 B-9 B-AC1 4 GA M0 C QT-1 FCV-63-40 2 C-9 B-ACT 4 GA M0 C QT-1 FCV-63-4 2 D-8 B-AC1 2' GL MO O QT-1 FCV-63-1 2 F-10 B-AC'1 12 GA M0 O CS* FCV 63-5 2 D-10 B-AC'I 8 GA MO O CS* FCV-63-22 2 D-6 B-AC7 4 CA MO O CS* FCV-63-47 2 E-10 B-AC1 6 GA MO O QT-1 FCV-63-48 2 D-10 B-AC1 6 GA MO O QT-1 FCV-63-175 2 D-8 B-AC1 2 GL M0 O QT-1 FCV-63-67 1 B-6 B-AC1 10 CA MO O CS* FCV-63-80 1 B-4 B-AC1 10 GA MO O CS* FCV-63-98 1 B-3 B-AC1 10 GA MO O CS* \\ C-24 . ena 4

.~ .me _^ Sequoyah Nuclear Plant inservice Valve Testing Program ~ SYSTEM: (AM S AFFTY TN TFOTTON SYSTEM DRAWING NO: 47k'811-1 (R20) e o6 >4 a: wo ~ VALVE qg 5@ f$ fa Sg q&N US idN REMARKS o TESTING h yU g NUMBER Nj dO U REQUIRED o M >b b ag y Wy u A FCV-61-6 2 F-10 B-ACT ~4 CA M0 C QT-1 FCV 63-7 2 F-lO B-ACT 4 CA M0 C QT-1 FCV-63-23 2 D-6 A-ACT 3/4 GA DIA 0 QT-1, SLT FCV-63-25 2 A-7 B-ACT 4 CA M0 C QT-1 FCV-63-26 2 B-7 B-ACT 4 GA M0 C QT-1 FCV-63-38 2 B-8 B-ACT 1 CL DIA 0 QT-1 FCV-63-71 2 C-6 A-AC7 3/4 CL DIA C QT-1 SLT FCV-63-84 2 C-6 A-AC1 3/4 CL DIA C QT-1. SLT FCV-63-94 2 C-7 B-AC1 8 CA M0 O CS* FCV-63-152 2 D-7 B-ACT 4 CA MO O QT-1 FCV-63-153 2 E-7 B-ACT 4 CA MO O QT-1 FCV-6 %156 2 ,E-6 E-ACT 4 CA MO C CS* FCV-63-157 2 D-6 B-AC1 4 GA M0 C CS* FCV-63-172 2 F-5 B-ACT 12 GA M0 C CS* FCV-63-93 2 C-7 B-AC 8 CA MO O CS* FCV-63-3 2 D-8 B-AC7 2 CL MO O CS* FCV-63-72 2 H-6 B-AC'I 18 CA M0 C CS* C-25

u Sequoyah Nuclear Plant inservice Valve Testing Program CAFFTY TNTE'TTON SYSTEM DRAWI!JG tJO: 47W811-1 (R20) SYSTEM: (60 C U Uo oe >4 n; VALVE g Uy yo fga @ L2 hO TESTI!JG d hU ga IJUMBER m ;j ,i O U d$ k$ REQUIRED U$ id $ REMARKS g@$gg g!g gg s s 1. u n. FCV-63-11R -1 B-1 B-ACT IC CA MO O CS* 63-502 2 F-10 C 12 CK SA CV-1 X ER See PV 63-510 2 D-10 C 8 CK SA CV-1 X ER See PV-4 Pump Test 63-524 2 E-8 C 4 CK SA CV-1 X ER See PV-5 Pump Test 63-526 2 D-8 C 4 CK SA CV-1 X ER See PV-5 Pump Test 63-543 1 F-4 AC 2 CK SA CV-1, SLTP X ER See PV-5 63-545 1 E_-. 4 AC 2 CK SA CV-1, SLTP X ER See PV-5 63-547 1 D 2+ AC 2 CK SA CV-1, SLTP X ER See PV-5 63-549 1 E-4 AC 2 CK SA CV-1, SLTP X ER See PV-5 AU-63-551 1 G-1 ACT 2 CK SA CV-1, SLTP X ER See PV-5 AC-63-553 1 H-3 ACT 2 CK SA CV-1, SLTP X ER See PV-5 63-555 1 G-3 bi 2 CK ' SA CV-1, SLTP X ER See PV-5 63-557 1 G-2 ki 2 CK SA CV-1, SLTP X ER See PV-5 63-558 1 E-3 C 6 CK SA CV-1, SLTP X ER See PV-5 63-559 1 _D-1 C 6 CK SA CV-1,'SLTP X ER See PV-5 AG-63-560 1 E-1 ACT 10 CK SA CS*, SLTP AG-63-561 1 D-2 ACT 10 CK SA CS*, SLTP 'TC - 63-562 1 D-3 art 10 CK SA CS*, SLTP C-76

Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (63) SAFETY TN.7FCTION SYSTEM-~ DRAWING NO: _47W811-1 (R20) 0 Y OH t4 n H O gy dy fg @g Q6 TESTING $1 Ig U VALVE g NUMBER (f j gO U 'C $ $$ REQUIRED U> N$ b u) e e oH O RD1 ARKS <o "8 >6 "8 W yy U 4 '\\C-63-563 1 F-2 ACT 10 CK SA CS*, SLTP 63-5811 1 E-7 C 3 CK SA CV-1 X ER See PV 63-586 1 E-1 C 185 CK SA CV-1 X ER See PV-6 1 63-587 1 D-2 C 14 CK SA CV-1 X ER See PV-6 1 61-588 1 D-3 C lb CK SA CV-1 X ER See PV-6 63-584 1 E-2 C lh CK SA CV-1 X ER See PV-6 AG-63-622 1 C-1 ACT 10 CK SA CV-1, SLTP X Yes See PV-7 63-623 1 C-2 ^'ECT 10 CK SA CV-1, SLTP X Yes See PV-7 AU-63-624 1 C-3 ACT 10 CK SA CV-1, SLTP X ygg See PV-7 ac-61-625 1 C-1 ACT 10 CK SA CV-1, SLTP X Yes See PV-7 AL-63-632 1 G-3 ACT 6 CK SA CS*, SLTP au-63-633 1 C-2 ACT 6 CK SA CS*, SLTP AL-63-634 1 G-3 ACT 6 CK SA CSA, SLTP ^ 63-635 1 G-2 CT 6 CK SA CS*, SLTP 63-640 1 F-4 ^'ICT 8 CK SA CS*, SLTP AL-63-641 1 F-2 ACT 6 CK SA CS*, SLTP AG-63-643 1 F-4 ACT 8 CK SA CS*, SLTP AC 63-644 1 D-2 5CT 6 CK SA CS*, SLTP I These valves have a SLTP Test on Unit 1; this test shall be deleted when Tecimical Specific. tions,are revised, C-27

Sequoyah Nuclear Plant inservice Vaive Testing Program SYSTEf4: (63) SAFETY INJECTION SYSTEM-DRAWING NO: 47W811-1 (R20) U N oe s m ~o gy U$ VALVE $a 8m jU TESTI!!G [*] hN y !;UtiBER Gj NO U d$ .h $ Q "N REQUIRED US fr! $ REMARKS 4o >a in >b bu o n O ww "8 6 W "8 W u,< s O A 63-602 3 A-1 C 1 REL SA C RF 63-603 3 A-3 C 1 REL SA C RF 63-604 3 A-4 C 1 REL SA C RF 63-605 3 A-6 C 1 R EI, SA C RF 63-676 2 G-7 C 2 REL SA C RF 63-627 2 G-7 C 2 REL SA C RF 63-637 2 F-6 C 3/4 REL SA C RF 63-534 2 E-7' C 3/4 REL SA C RF 63-535 2 D-7 C 3/4 REL SA C RF 63-536 2 D-7 C 3/4 REL SA C RF 63-511 2 D-10 C 3/4 REL Si C RF 63-570 2 B-8 C 1 CK ' SA SC* 63-530 2 D-8 C 3/4 CK SA CV-1 Pump Test 63-528 2 E-8 C 3/4 CK SA CV-1 Pump Test s ~6 ~. e w. -m

2 Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (6/) ESSENTIAL RAW'C00 LING UATER (R16) DRAWING NO: 47W845-1 U 5 0H >+ M ~ H o d$ VALVE m fa @w j U TESTING db yU o a mh fg q" ,c0 N d$ 'h $ 2 N REQUIRED U fd N REMARKS NUMBER 84 o NN >b t0 >b H O g O H yg "8 6 =0 M de .c U N FCV-67-67 3 C-7 B-ACT 6 BUT M0 C QT-1 Frv-67-65 3 C-7 B-ACT 6 EUT MO C QT-1 FCV-67-66 3 C-11 B-ACT 6 BUT M0 C QT-1 FCV-67-68 3 C-11 B-ACT 6 BUT MO C QT-1 6 h a l C-29

-.. ~. -....... -... u .D Sequoyah Nuclear Plant inservice Valve Testing Program SYSTE!!: (A7) FC FFWT AT FAU' COOT.TNG UATER DRAWING NO: 47W845'-l (R16) a 0H N I4 H 0 VALVE gy UN $o $ra Ow hU TESTI!!G kU to NUMBER (Ji j NO N d$ k "N REQUIRED U$ U$ REMARKS 4y >P W >b b8 O O "8 'd W "8 gM B" N I4 U k at n_r,7 6AoA 1 U-3 C 24 CK SA CV-1 Pump Test AERCW 0-67-669B 3 U-3 C 24 CK SA CV-1 Pump Test-AERCW FCV-67-12 3 E-1 R-ACT 36 BUT MO O QT-1 (AEpCW) l l, 3 D-1 R-ACT 36 EUT MO O QT-1 (AERCW) 360 3 E-2 3-ACT 24 BUT MO O QT_-1 (AERCW) 763 1 E-4 3-ACT 24 BUT MO O QT-1 (AERCW) 164 3 E-1 3-ACT 36 EUT MO O QT-1 (AERCW) 1As 1 D-1 3-ACT 36 BUT MO O QT-1 (gFprp) 166 3 E-3 B-ACT 24 BUT MO O QT-1 (AppCW) 367 3 E-3 B-ACT 24 BUT MO O QT-1 (AEpCW) 67-656A 3 E-2 C 30 CK SA CV-1 Pump Test AERCW 67-656B 3 E-3 C 30 CK SA CV-1 Pump Test AERCW FCV-67-361 3 E-2 B-ACT 30 BUT MO O QT-1 (AFRCM) FCV-67-362 3 E-3 B-ACT 30 EUT MO O QT-1 (AERCW) W C-30

..mA Sequoyah Nuclear Plant inservice Valve Testing Program CYSTEM: (67) ESSENTIAL RAW COOLINCr-WATER DRAWING NO: 47W845-2 (RIS) 0 Y 0 E4 >4 et wo gm 5 [j ~ VALVE yga @ ra kU TESTING $b hU g UUMBER 63 NO [j d$ "j $ kU REQUIRED U !d N REMARKS o M >b P Q p, y ag O A 4 FCV-67-151 3 C-6 B-ACT 24 BUT MO C QT-1 FCV-67-192 3 C7 B-ACT 24 BUT MO C QT-1 FCV-67-123 3 C-9 B-ACT 24 BUT M0 C QT-1 FCV-67-124 3 E-8 B-ACT 18 BUT M0 C QT-1 FCV-67-125 3 C-8 B-ACT 18 BUT M0 C QT-1 FCV-67-126 3 D-7 B-ACT 18 BUT M0 C QT-1 FCV-67-147 3 A-6 B-ACT 24 BUT M0 C QT-1 rrV-67-R1 3 U-10 B-ACT 24 BUT MO O QT-1 FCV-67-82 3 H-9 B-ACT 24 BUT MO O QT-1 FCV-67-127 3 B-10 B-ACT 8 BUT M0 O QT-1 FCV-67-128 3 B-10 B-ACT 8 BUT MO O QT-1 FCV-67-146 3 C-7 B-ACT 24 BUT MO O CS* FCV-67-223 3 A-6 C 24 BUT M0 C QT-1 FCV-67-424 3 A-9 B-ACT 24 BUT M0 O QT-1 FCV-67-478 3 B-7 B-ACT 24 BUT MO O CS* C-31

w. a Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (67) ESSENTIAL RAW ~ COOLING WATER DRAWING MO: _47W845-3 (R14) E S 0y N M so dn s$ $w 8m jU TESTING [I] ~ VALVE $q g j'" dd y d$ $$ h5 REQUIRED U$ y$U w IRJMBER j [d REMARKS h6 H ta >b 0 0"U $ M us WW "8 15 o FrV-67-141 A-4 A-AC1 2 GA MO O QT-1, SLT AU-67-580D 2 A-3 ACT 2 C SA CV-1, SLT FCV-67-142 2 A-4 A-ACT 2 GA MO O QT-1, SLT FCV-67-298 2 A-4 A-AC1 2 GA MO O QT-1, SLT 67-5R5D 2 A-4 ^ EAS h CK SA SLT TRCV FCV-67-138 2 B-4 A-AC1 2 CA MO O QT-1, SLT AL-67-580B 2 B-3 ACT 2 CK SA CV-1, SLT FCV-67-130 2 B-4 A-ACT 2 CA MO O QT--1, SLT FCV-67-297 2 B-4 A-ACT 2 CA MO O QT-1, SLT 67-585B 2 B-4 ^ PAS h CK SA SLT TRCV FCV-67-133 2 B-4 A-AC'l 2 CA MO O QT-1, SLT 67-580C 2 B-3 AC1 2 CK SA CV-1, SLT FCV-67-134 2 C-4 A-AC1 2 CA MO O QT-1, SLT FCV-67-296 2 C-4 A-AC'] 2 GA MO O QT-1, SLT Au-67-585C 2 C-4 PAF h CK SA SLT TRCV FCV-67-130 2 C4 A-AC': 2 CA MO O QT-1, SLT AC-67-580A 2 C-3 A n'! ? CK SA CV-1. SLT j FCV-67-131 2 C4 A-AC'l 2 CA M0 O QT-1, SLT 1 C-32

m. Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (67) ESSENTIAL RAW COOLING WATER DRAWING NO: 47V845-3 (R14) 0 W oe = g -o gM d$ VALVE $w 8w %O TESTING DM hU w nunnen as >.i a M

b m >e be o" O sq W B" ww A8 't5 W "8 U m 4 FCV-67-87 2 C-4 A-ACT 6 BUT MO O CS*, SLT M,- 67-575A 2 G-4 pas is CK SA SLT TRCV FCV-67-83 2 G-4 A-ACT 6 BUT MO O CS*, SLT AG-67-562A 2 G-4 ACT 6 CK SA CS*, SLT 9 m l k C-34 . _--.7 Sequoyah Nuclear Plant Inservice Valve Testing Program SYSTEM. (67) ESSENTIAL RAW COOLING WATER DRAWING !;O: 47W845-4 (R15) R D U os = me pg 5@ g$ fa @y 96 TESTIfG El b hU VALU y g h EWIE U HAMS !M BER 8 6 e =8 E M u A FCV-67-168 3 C-7 3-ACT 1h GA DIA O QT-1 FCV-67-170 3 C-9 B-ACT 1 CA DIA 0 QT-1 FCV-67-176 3 D-7 B-ACT 1 CA DIA C QT_ _1 FCV-67-182 3 D-9 B-ACT 1h GA DIA C QT-1 FCV-67-184 3 D-7 B-ACT 1 GA DIA C QT-1 FCV-67-186 3 D-9 B-ACT lh GA DIA C QT-1 FCV-67-188 3 E-7 B-ACT 1 GA DIA C QT-1 FCV-67-lon 3 E-9 B-ACT 1 GA DIA C QT-1 FCV-67-342 3 G-7 B-ACT 2 GA DIA 0 QT-1 FCV-67-344 3 G-9 B-ACT 2 CA DIA C QT-1 FCV-67-346 3 E-8 B-ACT 1h CA DIA O QT-1 FCV-6 7 ~44 8 3 E-9 B-ACT 1h GA ' DIA C QT-1 FCV-67-350 3 E-7 B-ACT l's CA DIA 0 QT-1 FCV-67-352 3 E-9 B-ACT 1h CA DIA C QT-1 FCV-67-354 3 F-7 B-ACT l!$ GA DIA O QT-1 FCV-67-356 3 F-9 B-ACT 1h CA DIA C QT-1 FCV-67-162 3 B-7 B-ACT 2 CA DIA O QT-1 FCV-67-164 3 B-9 B-ACT 2 CA DIA C QT-1 C-35 a Sequoyah Nuclear Plant laservice Valve Testing Program SYSTEM: (67) ESSENTIAL RAW COOLING-WATER DRTMING NO: 47W845-4 (R15) E 0 E-* Se Cd H O VALVE gg g 5@ $ra O ra jU TESTING D $,U ca [Ji'* j dO N .2 U REQUIRED U idO RD1 ARKS UUMBER !'4 $05 ME 50 "8 "O 0 A aC FCV-67-213 -3 B-7 3-ACT lb GA DIA O QT-1 FCV-67-215 3 B-9 3-ACT 1 GA DIA C QT-1 FCV-67-217 3 B-2 3-ACT 2 GA DIA O QT-1 FCV-67-219 3 B-4 B-ACT 2 GA DIA O QT-1 FCV-67-336 3 A-2 B-ACT 1 GA DIA O QT-1 Cycled FCV-67-338 3 A-4 3-ACT 1 CA DIA O QT-1 Cycled O e C-36 l, g l Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (67) ESSENTIAL RAW COOLIliG WATER DRAWING NO: 47W845-5 (R6) U S oe u e ~o ng y UN is "! e$ $ VALVE yy 8y %6 TESTING D yU m 2:3 as a y gg sg & "I: nrounten 3-ku numaxS i Nunnen 8 >e m >e de o u c 0 "8 6 W "8 d M So ww O A FCV-67-205 -3 G-9 B-ACT 6 BUT MO O QT-1 FCV-67-208 3 G-10 B-ACT 6 BUT }!0 0 QT--l 67-723A 3 B-3 C 24 CK SA CV-1 Pump Test 67-724A 3 B-3 C 24 CK SA CV-1 Pump Test 67-723B 3 D-3 C 24 CK SA CV-1 Pump Test 67-724B 3 D ~, C 24 CK SA CV-1 Pump Test 67-743A 3 G-3 C 24 CK SA CV-1 Pump Test 67-744A 3 c-3 C 24' CK SA CV-1 Pump Test 67-743B 3 F-3 C 24 CK SA CV-1 Pump Test 67-744B 3 E-3 C 24 CK SA CV-1 Pump Test FCV-67-489 3 D-4 B-ACT 24 BUT MO O QT-1 FCV-67-492 3 B-4 B-ACT 24 BITT

  • MO O

OT-1 C-17 A Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (63) RFACTOR COOLA!!T SYSTEM " DRAWIt:G 1:0: 47W813'-1 (R16) o p eU a: r; o g U !! $ r.: 8m QU TESTIt:G hn [j ~~i VALVE h ;$ rg w ? 'j

j !.3 M
j" f,
"II nEQUIRED

[j $ [4y notAngs j ffUttitER J E. > i: p i~ og tj ,f = il

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.c o no o o ww !2 t; " o a ,c Fev-68-117 -1 B-3 !!-ACT 3 CA MO O QT-1 PCV-68-340A 1 E-3 3-ACT 3 CL DIA C QT-1 PORy l PCV-68-112 1 E-3 3-ACT 3 CA MO O QT-1 PCV-68-334 1 E-3 B-ACT 3 CL DIA C QT-1 pony I 68-561 1 A-3 C 6 REL SA C RF 68-564 1 A-4 C 6 REL SA C RF 68-565 1 A-4 C 6 REL SA C PF l l l l e h C-38 ~.. -........... e Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (AO DFarTon coht Ah"r SYSTFM (R21) DRAWING 110: 47k'830-6 o m d (( y@ VALVE $r4 O ra TESTIt:G Dt to ?q h ra W ds d0 t2 NUMBER hO hh N {$ ,h h" QA QUIED 43 REMARKS

  • C n.

w No N $ $H 8 D ,c ~o U A 4 FCV-68-305 2 C-6 1-ACT '3/4 CL DIA O QT-1, SLT FCV-6'3-64 2 B-5 A-ACT 1 GT, DIA C QT-1, SLT AC-77-868 2 C-6 ACT 1 CK SA CS*, SLT AC-77-849 2 B-6 ACT 1/4 CK SA CS*, SLT t Ts e -- h er g C-39 e n ~ r ? 1: y te 1 v. c. t "A 6 i s p 1 4 s E i o= E a G = 6 3 ) G O o w Ii m C 0::IIS21 (4 2AI1Y:Td51'IV I, 'l Q C b l IS2n52H O l' a'2I'I2H I G 1 99 b b j cd m m 0 PM o .o 88 I sa i i I c w O I W t;OIIISOd c o .C MiC:1 e I .e e 3dA1 C HO1VPlOV E 3 Q 1 2dA1 b 2NIVA C C M. Q x x ( ,ZIS a w s o L r m 3 d 2 AHOD31Y3 D D .C v: 2NIVA <i / Y. 'l A S21V!iICTdOO3 i 7 O p c;;1p,yua e 4 3 C O' g g SSTIO (f) E 2;;SV C< W EL O T 4: w yg b at >W C C Ac r e l I >Zg 0; 1 g e e W i

  • 1 P

v r to L C } D L L1 i 2 = Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (70) COMPONET COOT.ING SYSTEM DRAWING 1:o:z.7pg59_'1 (gj7) U S' oH d4 et g wo gy U$ I.3 $ ~ VALVE [.3 Ow o${.' N 7 U TESTING !3 y hU w ga 3

  • C
  • NUM13ER Gi j Ib" dO U

>d " h$ REQUIRED UD id N REMARKS 4o O >b v2 a8 6 "U g M" ww U.:" .c u a 70-751 1 F-4 C R CK SA CV-1 70-578 3 E-3 C 4 REL SA C RF 70-504 3 E-8 C 16 CK SA CV-1 Pump Test 70-504A 3 C-8 C 16 CK SA CV-1 Pump Test 70 RO4P 3 D-R C 16 CK SA CV-1 Pump Test 8 C-41 =.. m Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (70) COMPONENT COOLING SYSTEM DRAWI!!G 120: _47W850-1 (R12) A 0 oa c: wo rg y U$ VALVE $w 0m hU TESTIt:G !3 b U !JUMBER hj NO M d$ $ A* 2 f$ REQUIRED U$ !y $ w d REMAR4 Oh N h$ U Qg U 4 4 FCV-70-66 3 E-3 il-ACT 2 AN DIA 0 QT-1 FrV-70-?O7 3 A-2 B-ACT 10 BUT M0 O QT-1 FCV-70-197 3 B-6 3-ACT 20 BUT M0 O QT-1 FCV-70-398 3 B-6 3-ACT 20 BUT MO O QT-1 FCV-70-206 3 C-10 3-ACT 10 BUT MO O QT-1 FCV-70-194 3 B-4 3-ACT 20 BUT MO O QT-1 FCV-70-193 3 B-4 3-ACT 20 BUT MO O QT-1 FCV-70-203 3 B-1 3-ACT 10 BUT MO O QT-1 FCV-70-1 3 H-6 3-ACT 12 BUT M0 C QT-1 FCV-70-11 3 W5 B-ACT I? BUT MO O OT-1 C-42 - -=. . ~.... a Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (70) COMPONENTCOOLINGS[ STEM DRAWING No: 47k'859-2 (R14) U oa a: so g 5@ }$ VALVE m @w 8w jU TESTING Db ,$ U w NUMBER (f j ,; O d d$ 'j $ 2]U h! $ REMARKS U{ REQUIRED 'o >!j M H H g y y og U 4 ,C 4G-70-698 2 E-9 PAS 4 CK SA SLT TRCV ar,- 70-679 2 11 - 4 ACT 3 CK SA CS*, SLT \\C-70-687 2 11 - 9 PAS b CK SA SLT TRCV r\\C-70-692 2 G-4 ACT 6 CK SA CS*. SLT FCV-70-143 2 E-3 A-ACT 6 BUT MO O QT-1,SLT FCV-70-85 2 D-10 A-ACT 6 BUT MO O QT-1,SLT e C-43 t a.e =s.

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Se.quoyah Nuclear Plant inservice Valve Testing Program S':: ZEM : (70) COMPONENT COOLING SYSTEM DRAWING NO: _47W859-2 (R14) I u 9 0B N M H C VALVE qy U$ $a 8a jU TESTING Dy !y U ~ g w !FJf1BER di j NO U d$

  • C $

2 N REQUIRED UD dN REMARKS 4o >}} Wg y W >b H g ag U N 4 ,\\C-70-703 -3 D-4 ACT 3 REL SA C RF, SLT rcV-70-1/.0 2 C-3 T-ACT 6 BUT MO O CS*, SLT FCV-70-134 2 H-3 ,\\-ACT 3 GA MO O CS*, SLT FCV-70-89 2 E-9 A-ACT 6 BUT MO O CS*, SLT FCV-70-42 2 E-10.\\-ACT 6 BUT MO O CS*, SLT FCV-70-90 2 E-10 ,\\-ACT 6 BUT MO O CS*, ST.T FCV-70-87 2 H-9 <\\-ACT 3 CA M0 O CS*, SLT e S g k

  • I$

w d Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (70) COMPONENT COOLING S[STDI DRAWING !;O: _47V859-4 (R7) N 0H (4 H O VALVE DJ $ bN hO U TESTING b [y U DJ M f W NUMBER [2 j [* " 7O N 3

  • C $

$! "N REQUIRED UD d$ REMARKS go N Se 9 m o a ww "8 6 W "8 W B" u A FCV-70-151 3 F-3 3-ACT 18 EUT M0 C QT-1 FcV-70-156 3 F-4 3-ACT 18 BUT MO C QT-1 k C-45 ...-_==_==a a Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (7?) CONTAINMENT SPRAY SYSTEM DRAWIr:G 110: 47W812'-1 (R11) E te s u n: ~ < > q 5@ g$ 3 VALVE m 7U TESTIt:G hb !jU $u Ou u h{N yy y 1: UMBER 03 O N ll$ d$ REQUIRED "a !N REMARKS p b H o ~ f FCV-72-7 '2 B-4 A-ACT 12 CA M0 C QT-1, SLT 5 FCV-72-21 2 B-10 B-ACT 12 CA MO O QT-1 FCV-72-22 2 D-10 B-ACT 12 GA MO O QT-1 FCV-72-39 2 D-4 A-ACT 12 GA M0 C QT-1, SLT FCV-72-40 2 E-4 B ACT 8 GA M0 C CS* FCV-72-41 2 F-4 B-ACT 8 GA MO C CS* 72-528 2 D-7 C 12 CK SA CV-1 pim.n Test 72-529 2 B-7 C 12 CK SA CV-1 p,m.n Test 72-547 2 D-3 C 12 CK SA CV-1 k Yes See PV-10 72-548 2 B-3 C 12 CK SA CV-1 x yes son Pv-10 72-555 2 F-3 C 8 CK SA CV-1 X Yes See PV-10 72-556 2 E-3 C 8 CK SA CV-1 X Yes See PV-10 FCV-72-13 2 E-7 3-ACT 2 CA MO C QT-1 FCV-72-34 A 2 C-7 'i-ACT 2 CA M0 C QT-1 72-506 ? D-9 C 17 CK SA CV-1 Pimm Tent 72-507 9 ko e 17 cv m cv-] Pump Test FCV-72-20 2 B-9 B-ACT 17 CA MO O OT-1 FCV-72-23 2 D-9 B-ACT 12 CA MO O QT-1 C-46 Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (74) RESTDUAL 11 EAT ~ REMOVAL SYSTEM DRAWIt1G NO: 47W810-1 (Rll) 0 08 M N p HD UN $w 0m h~ by hU O TESTING VALVE M p2 gO U d$ i;l 5 REQUIRED Ug I4 N REMARKS NUMBER NO >H m >H db H O b WW "8 6 W "O yM B" H w o" O =a ga no Nw as e O 4 rC FCV-81-12 2 C-4 A-ACT 3 CA DIA 0 QT-1, SLT AC 81-502 2 G-4 ECT 3 CK SA CS*, SLT ) G f \\ C-51 ... ~. =.. -. =. ~. - Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (84) FTOOD MODE'BORATION DRAWItY,130: 47W809-7 (R7) O S OP D: H 0 b' hO VALVE M p U TESTI!;G Dy NU D.2 M W W !! UMBER E, f d O N" d" se >D g$ [2 ~5 REQUIRED "2 D a REMARKS c o o w e o's gM U" Ww 8 6 u 84-511 2 F-8 A-PAS 1 CA M LC SLT 9 mem 8 e O C--5 2 m.._..-.._.._.. Sequoyah Nuclear Plant Inservice Valve Testing Program SYSTEM: (87) UPPER FFAD TNTFCTIO I SYSTEM DRAWI!;G !;O: 4 7k'811-2 (R9) D oe .~ m -o U !! $o $u 8u jU VALVE TESTI!IG $1 Nd 5y u u dB u d <$ aC nEeurnEo 3$ Et; REnAPxS =" r:unsER <c IER Re o-o >e u >e 8 6 W "8 gW B" wa U A .C FCV-87-21 2 E-6 B-ACT 12 GA CYL 0 QT-1 FCV-87-22 2 E-7 B-ACT 12 CA CYL 0 QT-1 FCV-87-23 2 F-6 B-ACT 12 CA CYL O QT-1 FCV-87-24 2 F-7 B-ACT 12 CA CYL 0 QT-1 FCV-87-7 1 E-3 A-ACT 2 CL DIA C QT-1, SLT FCV-87-8 1 E-3 T-ACT 2 GT, DTA C OT-1, ST.T FCV-87-9 2 E-4 A-ACT 2 GL DIA C QT-1, SLT FCV-87-10 2 F-3 B-ACT 3/4 GT, DTA C OT-1 FCV-87-ll 2 F-5 B-ACT 2 GL DIA C QT-1 AC-87-558 1 E-1 ACT 8 CK SA CS*. ST.TP See PV-11 At.,- 87-559 1 F-1 ACT 8 CK SA CS*, SLTP See PV-11 ^ 87-560 1 F-2 CT 8 CK SA CS*, SLTP See PV-11 AC-87-561 1 C-2 ACT 8 CK SA CS*, SI.TP See PV-11 AC-87-562 1 E-4 ACT 12 CK SA CS*. ST.TP See PV-ll AC-87-563 1 F-4 ACT 12 CK SA CS*. ST.TP See PV-11 87-556 2 C-7 C 1h REL SA C RF 87-557 2 C-10 C lh REL SA C RF e C-53 R s u Y p s t T u E r N M e UV MA D B L EV i ( s RE 8 k 7 ) L T PE R <$w S 2 H e u$g E A qu D B "gf'3o I o 7 o8"8$eO U y EC a T h P;, I D O 6b8$> N N S u Y 1 S c 2 WOa T l D e I a R Sd$ D r b*Cy P la S 5p<S= C A n P$g t 5 4 i =02];3 - n C s A8"5o e R r R v D ET US c i QE I T e FI EN DG Va lv "9U U e W"Sb T e <dWN$~ S s t eW$do in g P r D o RA g W r I a t m 0 1: R o E M A 4 R 7 K k S 8' 1 1 ~ 2 ( R 9 ) O Sequoyah Nuclear Plant inservice Valve Testing Program SYSTEM: (00) RADTATION MONITORING SYSTDI DRAWI!!G 1:0: 47k'610-90-3 0 OH N c: H O VALVE qy 3 *! $w Ow jU TESTING ${ b U y[2 $ w l'UM13ER di j NO O d$ fe 5 REQUIRED U $s $ EU E!E $5 REMARKS 8 "O U A FCV-90-107 2 A-9 A-ACT lb CA DIA O QT-1, SLT _ FCV-90-108 2 C-9 A-ACT lh GA DIA O QT-1, SLT FCV-90-109 2 C-9 A-ACT 1 CA DIA O QT-1, SLT FCV-90-110 2 C-9 A-ACT Ib CA DIA O QT-1, SLT FCV-90-111 2 D-9 A-art 14 cA nTA o OT-1. si T FCV-90-113 2 A-6 A-ACT 1 CA DIA O QT-1, SLT FCV-90-114 2 C-5 A-ACT lb CA DIA O QT-1, SLT FCV-90-115 2 C-5 A-ACT 1 CA DIA O OT-1. SLT FCV-90-116 2 C-5 A-ACT 13< cA nTA o OT 1 si T FCV-90-117 2 D-6 A-ACT lb CA DTA O OT-1. ST T 0 C-55 i i a h L PV-1 5f [ System: Chemical and Volure Control System 4 Valve: 62-525, 62-532 9 i Class: 2 Category: C Function: Opens to admit charging pump flow to the boron injection j tank during safety injection. Impractical Requirement: Exercise valve at full flow on a quarterly tasis. .lI'l 1 Basis for I Relief: The centrifugal charging pumps cannot be run at full flew I during operation for charging or through the cold leg injection lines due to undesirable temperature and/or i boron concentration transients. I f Alt. Testing: Test valve at normal charging flow quarterly and verify that { it will open to pass at least the minimum design required flow during each refueling. Frequency for Alt. 4 Testing: Part stroke quarterly and full stroke at refueling. 4 1 6 t C-56 2 d ] e { 4 D t .h E S 1 4f PV-2 System: Chemical and Volume Control System Valve: 62-504 [ Class: 2 4 j Category C. 1 Function: Opens to admit flow from refueling water storage tank to j the centrifugal charging pumps.. i Impractical Requirement: Exercise quarterly at full flow. e Basis for Relief: Charging pumps cannot be run at full flow taking suction 1 ; from the RWST without causing undesirable RCS temperature i. and/or boron concentration changes. n.7 Alt. j Testing: Exercise at full flow at refueling during system performance i tests and part stroke at reduced flow during cold shutdown. i. { Frequency .g for Alt. ' ? Testing: Full stroke once per refueling and part stroke during cold i shutdown (but not more often than every nine months for + Unit 1 and three months for Unit 2.) i 4 1 4 v j 1 1 i t e 1 -l i C-57 _ -_-~_ i I 9 PV-3 9 't System: Safety Injection System i Valve: 63-502 lj Class: 2 Category: C Function: Opens to admit flow fron RWST to the RHR pudps during safety injection. j Impractical Requirement: Exercise valve quarterly at full flow. n ]'!g Basis for Relief: The RHR pumps do not develop sufficient head to pump to it the reactor at normal operating pressures. The pump ] recirculation flow path does not include this check 2 valve. The refueling cavity dewatering line cannot be 3, used because the valve alignment required to use it results in degrading both trains of RHR. Capabilities j of the letdown system preclude use during cold shutdowns. Alternate Testing: Exercise at refueling mutages during system performance tests. Verify check valve backseats (for recirculation ECCS mode) during cold shutdowns. Frequency for Alt. Testing: Exercise once per refueling. Backseat during cold shutdown but not more often than every nine months for Unit 1 and three conths for Unit 2. i ~ C-58 I ? 5 r I PV-4 Ij System: Safety Injection System Valve 63-510 Class: B Category: C-Function: Opens to admit flow from RUST to the SIS pumps during g safety injection. Impractical J Requirement: Exercise valve quarterly'at full flow. !I j' Basis for 3 Relief: SIS pumps do not develop sufficient head to pump to the [ RCS at normal operating pressures and the pump recirculation j' line will not pass full flow. RCS letdown capability will not allow pumps to be run at full flow during cold shutdcwn. c f) Alternate ? Testing: Cycle valve at reduced flow once per quarter during SIS I pump test and at full flow once per refueling during system i performance test. Frequency ,j for Alt. Testing: Part Stroke quarterly, full stroke once per refueling. 1 l r g 9 4 e 4 C-59 l l l 1 {# PV-5 System: Safety Injection System i Valve: 63-524, 63-526, 63-547, 63-559, 63-549, 63-5$8, 63-545, { 63-543, 63-557, 63-551, 63-555, 63-553. Class: 1 (except 63-526 and 63-524 which are classj2). Category: C Function: Opens to admit flow from SIS pucps to RCS during LOCA. Icpractical Requirement: Exercise at full flow on a quarterly basis. l Basis for l Relief: SIS pumps do not develop suf ficient head to overcome nortal ~ j RCS pressure. Use of another pump would result in an j undesirable temperature transient in the RCS. Letdown capability will not allow full flow testing with reactor head on. Alternate Testing: Part stroke valves during cold shutdown and exercise valve-(full stroke) at refueling during system performance test. Frequency i for Alt. j Testing: Part stroke during cold shutdown (but not more often than every nine conths for Unit 1 and three renths for Unit 2) and full stroke once per refueling. d ,e 4 4 C-60 e t' T it-PV-6 p System: Safety Injection System F Valve: 63-581, 63-587, 63-588, 63-589, 63-586 h <[ Class: 1 } Category: C i Function: Open to admit flow from boron injection tank to the RCS during safety injection. i . Impractical Requirement: Exercise valve on a quarterly basis at full flow. I g. Basis for ' t. Relief: RCS letdown capacity will not allow full flew injection { with the reactor vessel head on. Valve cannot be part stroked without discharging heavily borated water from y V the boron injection tank to the reactor. This would { cause an undesirable temperature and baron concentration 5 transients which could result in a safety injection or y unit trip. If the BIT and injection lines are not flushed completely to the vessel, boron plateout will ~ ( occur in the non heat-traced portion of the injection lines. Alternate } Testing: Part stroke valve during cold shutdown and exercise valve - at full flow during refueling du"ing system performance tests. Frequency for Alt. Testing: Part stroke valve during cold shutdown (but not more of ten than every nine months for Unit 1 and.three. months for y Unit 2) and once -per refueling (full ' stroke). s I* F l d l4 C-61 l i a PV-7 System: Safety Injection System Valve: 63-622, 63-623, 63-624, 63-625 i class: 1 Category: C i Function: Opens to admit flow from cold leg accumulators to the j RCS during safety injection. Inpractical Requirement: Exercise quarterly at full flow. ] Basis for Relief: These valves cannot be cycled at full flow without removing the fuel from the core, removing the internals package and causing a rapid depressurization of the RCS from above 650 psig to atmospheric pressure. This is an unreasonable burden and could cause damage to the reactor vessel. Alternate ~ Testing: Exercise at reduced ficw using an SIS pucp through the check valve test lines to verify that the valve is not i stuck closed during cold shutdown. Frequency for Alt. Testing: During cold shutdown (but not core often than every nine conths for Unit 1 and three conths for Unit 2). 1 1 C-62 s\\ 'l/ l<. 1 e aj vv-8 ,I System: Main Feedwater i Valve: 3-508, 3-509, 3-510, 3-511 I i Class: 3 Category: C Function: Opens to admit main feedwater flow. 4 Impractical } Requirement: Exercise quarterly. 2 -1 Basis for 3 Relief: Exercising during power operation would result in 3 severe SG level transients and unit trip. During I hot standby and hot shutdown conditions, use of the j auxiliary feedwater system exercised these valves to the closed position, i I Alternate } Testing: No further testing deemed necessary. J t 4 S 4 C-63 i k PV-9 e System: Auxiliary Feedwater Valve: 3-805, 3-806, 3-810, 3-891, 3-892 kr Class: 3 Category: C Function: Opens to admit auxiliary feedwater flow or steam flow to auxiliary feedwater purps. The first three valves above also closes when the ERCh' is aligned to the auxiliary feedwater pump suction. Impractical ~ s Requirement: Exercise valve quarterly at full ficw.

(

Basis for Relief: Exercising these valves during power operation would ~ result in severe thermal shock to the auxiliary feedvater nozzles and cause SG level transients and a unit trip. Alternate Testing: These valves will be part stroked during the associated purp test. Routine operation of the auxiliary feedwater syster during hot standby and hot shutdown also exercises these valves. The first three valves will be backseated during }. cold shutdown. Frequency for Alt. Testing: Quarterly. I I J e e C-64 -.i) ? 4-i L PV-10 l System: Containment Spray e Valve: 72-547, 72-548, 72-555, 72-556 f Class: 2 .t Category: C ~ Function: Opens to admit flow from the containment spfay and RER pumps to the spray headers. Impractical f: Requirement: Exercise quarterly at full flow. A II Basis for [ Relief: Testing these valves with water will deluge the containment. j Testing with air could set off a containment isolation signal from high, high containment pressure.- t 4 Alternate Testing: Test with air during spray head nozzle test.. j Frequency i for Alt. Testing: At least once every five years. T 4 .i ( k i ! I l l: 0 1 1 .k ~ C-65 ~ d } i -t 6 g PV-ll i t System: Upper Head Injection System Valve: 87-558, 87-559, 87-560, 87-561, 87-562, 87-563 h Class: 1 j Category: C Function: Opens to admit Upper Head Injection fluid to reactor I vessel during rapid depressurization. l .g Impractical. Requirement: Exercising at full flow quarterly. U W h Basis for 'f Relief: Plant was not designed to' allow full flow inservice

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testing. To test at full flow it would be necessary 'f at the minimum to remove all fuel, remove reactor i internals, install a temporary impingement plate and '} drain the reactor coolant system. The resultant extended down time due to additional fuel movement' and storage problems, and water chemistry clean up and refill operations presents an unbearable operational. i burden. t i Alternate f.. Testing: Exercise valves at reduced flow during cold shutdown.' Frequency for Alt. Testing: Once per cold shutdown not to exceed once per nine months on Unit'l and three months on Unit 2.in case of frequent 8 cold shutdowns. n 1 1 4 4 C-66 .~ i a .i l PV-12 e i ! System: Auxiliary Feedwater Valve: 3-820, 3-821, 3-830, 3-831, 3-832, 3-833, 3-861, 3-862, {j 3-864, 3-871, 3-872, 3-873, 3-874, 3-921, 3-922 4 l f Class: 3 Category: C ~ Function: Opens to admit flow to Steam Generators. '.. i Impractical it Requirement: Exercise quarterly at-full flow. 11 Basis for

l Relief

Exercising these valves during power operation would result { in severe thermal shock]to the auxiliary feedwater nozzles 3 and cause SG 1evel transients and a unit trip. These valves ? are routinely operated during operation of the auxiliary 3 feedwater system during hot standby and hot shutdown. Alterrate j Testing: No further testing deemed necessary. I

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i APPENDIX D kr. E CONDITIONS E VALVES TESTED ONLY DURISG COLD SHUTDOW' v k Valves listed in Table D-1 are therein specifically identified by the Licenses f as valves which cannot be exercised during power operation, per Section X1, The table ~ lists the System, Valve Sunber, and the Easis Article IWV-3412(a). for Cold Shutdcwn Testing for each valve listed in Appendix C which is being a tested on a cold shutdown frequency. @jj 1! ?. I k ~ s 1 C e D-1 i .x 1 s' g + s f kl 5 F { TABLE D-1 I 4 SYSTEM VALVE BASIS FOR COLD SHUTDOWN TESTING Main Steam FCV-1-17 Closing these valves during power FCV-1-18 operation causes a loss of steam to the steam-driven Auxiliary 5 Feedwater Pu=p. 1 Main Steam PCV-1-5 Opening valve during power it PCV-1-12 operation will cause a steam i, PCV-1-23 generator level transient which { PCV-1-30 could result in an inadvertent 4 safety injection signal. er Feedwater FCV-3-33 Exercising these valves during f FCV-3-47 power operation causes a loss I FCV-3-87 of feedwater to the loop they i FCV-3-100 supply. Chemical and FCV-62-61 Exercising valves during operation Volume Control FCV-62-63 would cause loss of seal water return [ System and probable damage to the reactor coolant pump seals. t. I Chemical and FCV-62-98 Exercising valves during operation Volume Control FCV-62-99 results in isolation of the miniflow System path of the centrifugal charging pumps and could result in pump damage. jf Chemical and FCV-62-132 Stroking thesc valves during power Volume Control FCV-62-133 operation would cause unacceptable System LCV-62-135 boron transients. 5 LCV-62-136 J Safety Injection FCV-63-1 Exercising valve during op4 ration results System in losing suction from RWS1 to both trains of residual heat remaval. Safety Injection FCV-63-5 Exercising the valve during operation System isolates both SIS pump suction lines 1 from the refueling water storage tank. N 1 ~ D-2 f-$ i ,5 2 TABLE D-1 (continued) , 5- 'h SYSTEM VALVE BASIS FOR COLD SHUTDOWN TESTING Y t Safety Injection FCV-63-22 Exercising valve' quarterly isolates i System both trains of safety injection from .f. their normal flow path to the cold legs. I Safety Injection FCV-63-3 Exercising valve during operation-results .j System in isolating the recirculation line to i both trains of pu=ps. If the pumps started without recirculation, severe damage to both pumps could occur. j = Safety Injection FCV-63-156' These valves are normally closed and 4 System FCV-63-157 isolates the hot leg injection flow paths. FCV-63-172 Opening.these valves during operations results in the inoperability of the cold \\I leg injection path to provide 'its required [ flow rate. t Safety Injection .FCV-63-93 Closing these valves during operaticn r System FCV-63-94 'results in less than the required-number of RHR cold leg injection flow paths operable. 3 Safety Injection FCV-63-72. These valves are associated with the System ,73

Containment Su=p and their operation 8

during power operation could cause 11 flooding of. Lower Contain=ent. 9 Safety Injection 63-570 Exercising this valve during power operatic: System 'could cause unacceptable boron concentratic: changes in the boron injection tank. Safety Injection 63-563 These valves are in the residual heat remova: System 63-560 pump injection lines and the RER pu=ps do nc-63-561 . develop sufficient head to open the valve s 63-562 during operation. Injection through these 63-635 lines using another pump would result in 63-633 over-pressurization of the RHR lines behind 63-632 the check valves'and cause an undesirable 63-634 temperature transient in the RCS which 63-640 would cause a safety injection. 63-641 63-643 63-644 4 D-3 I r s' t t if L f TABLE D-1 (continued) h SYSTEM VALVE BASIS FOR COLD SHUTDOWN TESTING Safety Injection FCV-63-67 These valves are normally open during [ System FCV-63-80 operation with power. removed and under { FCV-63-98. administrative controls.. Their active g FCV-63-118 safety function exists only when RCS pressure is below 700 psig during the ij startup sequence. Exercising during j operation involves removing the adminis- ,g trative controls on the power supply and closing a normally open valve. s '. i i Essential Raw FCV-67-146 Failure of these valves in the closed k Cooling Water FCV-67-478 position would result in loss of ecoling System to the RCP oil cooler, thermal barriers, [ and seal water HTX. [ Essential Raw FCV-67 Exercising valve quarterly causes a loss Cooling Water FCV-67-87 of flow to control rod drive cooler's and System FCV-67-88 reactor coolant pump motor coolers. FCV-67-91 i FCV-67-95 FCV-67-96 i FCV-67-99 FCV-67-103 FCV-67-104 FCV-67-111 FCV-67-107 N-FCV-67-112 Essential Raw 67-562'A/B/C/D These valves normally pass water to the 3 Cooling Water ccntrol rod dr.ive coolers, and the + System reactor coolant pump. motor coolers. Exercising the valve causes a loss of flow to this equipment. Component Cooling FCV-70-140 Exercising valve during operation results System FCV-70-92 in loss of cooling water flow to all FCV-70-89 eight reactor coolant pump oil coolers. 4 o p_4 .) 1 } '$t Il [ TABLE D-1 (continued) h SYSTDI ""MES BASIS FOR COLD SHUTDOWN TESTING ~ l Component Cooling FCV-70-134 Exercising valves'during operation System FCV-70-87 .results in loss of cooling water flow f FCV-70-90 to all four reactor coolant pump thermal barrier coolers. .g Component Cooling 70-679 This valve normally passes water to System the thermal barrier coolers. Removal-from service for testing will caush a loss of flow to all-four TB coolers, 1 thus introducing the possibility of j seal failure on all four reactor coolant. pumps. 71I Component Cooling 70-692 This valve normally passes flow to the System reactor coolant pump oil cooler. Removal from service for. testing while RCPts are-running vil result in overheating-and i subsequent loss of all four RCP's. Containment Spray FCV-72-40 These valves are associated with the .y System FCV-72-41 Containment Sump. Exercising these valves ~ during operations could result in flooding of lower containment. Residual Heat FCV-74-1 Valves have interlocks to prevent opening Removal .FCV-74-2 them when RCS is above the RHR design 4 3 temperature and prassure. Exercising valve during operation results in over-pressurizing RHR. %~ Reactor Coolant 77-868 Closing these valves during power operation System 77-849 shuts down nitrogen supply inside contain-ment to a number of components and systens. j Primary Water 81-502 Exercising this valve results-in loss of System primary water to the RCP stand pipes and ?- PRT. ,b O e 4 4 D-5 i b U b -[ feI TABLE D-1 (continued) {.Io ( SYSTEM VALVES BASIS FOR COLD SHUTDOWN TESTING 1 Upper Head 87-558/559 Exercising these valves during power j Inj ection 87-560/561 operation would necessitate removal of 87-562/563 both trains of Upper Head Injection from, t, service to prevent over-pressurization of O UHI during the test.~ The test flow path .lj would require charging flow to be distri-4 buted to the UHI Check valve test line I which would present severe thermal shock problems. 1

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